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Category:NOTICE OF VIOLATION OF A REGULATION
MONTHYEARML20198M1681998-01-0909 January 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:As of 970711,licensee Failed to Establish Adequate Controls for Activities Affecting Quality of EDGs ML20141D5561997-06-20020 June 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $210,000.Violation Noted:Less than Four Independent DGs Were Operable & Neither Unit Was Placed in Hot Shutdown ML20136J3651997-03-14014 March 1997 Notice of Violations from Insp on 970114-0224.Violations Noted:Operators Failed to Ensure Automatic Actions Occurred After Unit 2 Recomb Discharge H2 Conc Hi-Hiannunciator Alarmed & After Grab Sample Show H Concentration of 8% ML20149J2871996-02-0909 February 1996 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.Violation Noted:Pp&L Discriminated Against Senior Security Officer After Concerns to NRC in 1992 Re Administration of Security Requalification Exam ML20247K6691989-05-19019 May 1989 Partially Withheld Notice of Violation Resulting from Investigation to Determine Whether Willful Matl False Statement Was Made in Physical Security Plan (Ref 10CFR2.790(a)) ML20148A5861988-03-14014 March 1988 Notice of Violation from Insp on 880104-0213.Violation Noted:On 880112,areas W/Dose Rates of Up to 400 M/H,Which Constitute High Radiation Areas Not Posted as Required ML20211B1211987-02-0909 February 1987 Notice of Violation from Insp on 861202-870105 ML20202F3161986-04-0404 April 1986 Notice of Violation from Insp on 860203-0314 ML20054F1921982-05-28028 May 1982 Notice of Violation from Insp on 820322-0402 1998-01-09
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARPNO-I-99-028, on 990608,Susquehanna Unit 2 Automatically Shut Down from 100% Power,Due to Failure in a Main Transformer. Region I Public Affairs Prepared to Respond to Media Inquires.Resident Inspectors on-site & Responded1999-06-0909 June 1999 PNO-I-99-028:on 990608,Susquehanna Unit 2 Automatically Shut Down from 100% Power,Due to Failure in a Main Transformer. Region I Public Affairs Prepared to Respond to Media Inquires.Resident Inspectors on-site & Responded ML20198M1681998-01-0909 January 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:As of 970711,licensee Failed to Establish Adequate Controls for Activities Affecting Quality of EDGs ML20141D5561997-06-20020 June 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $210,000.Violation Noted:Less than Four Independent DGs Were Operable & Neither Unit Was Placed in Hot Shutdown IR 05000387/19970011997-03-14014 March 1997 Insp Repts 50-387/97-01 & 50-388/97-01 on 970114-0224. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20136J3651997-03-14014 March 1997 Notice of Violations from Insp on 970114-0224.Violations Noted:Operators Failed to Ensure Automatic Actions Occurred After Unit 2 Recomb Discharge H2 Conc Hi-Hiannunciator Alarmed & After Grab Sample Show H Concentration of 8% ML20216B7331997-01-30030 January 1997 Investigation Rept 1-96-039 on 961018.No Noncompliance Noted.Major Areas Investigated:Review of PP&L Internal Investigation & Audit Repts Re Failure of NPO to Detect Misalignment of E DG Breaker from 960614 to 0704 ML20149J2871996-02-0909 February 1996 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.Violation Noted:Pp&L Discriminated Against Senior Security Officer After Concerns to NRC in 1992 Re Administration of Security Requalification Exam PNO-I-93-059, on 931026,unexpected Drop of Section of Refueling Mast Occurred While Lowering Bundle in Core.Maint Investigated & Discovered Bend in Mast.Licensee Determined Fuel Bundle Did Not Drop During Event1993-10-29029 October 1993 PNO-I-93-059:on 931026,unexpected Drop of Section of Refueling Mast Occurred While Lowering Bundle in Core.Maint Investigated & Discovered Bend in Mast.Licensee Determined Fuel Bundle Did Not Drop During Event IR 05000387/19900131990-07-11011 July 1990 Insp Repts 50-387/90-13 & 50-388/90-13 on 900625-29.No Violations Noted.Major Areas Inspected:Licensee Radiological Environ Monitoring & Radioactive Effluent Control Programs, Including Mgt Controls & Calibr of Effluent Monitors IR 05000387/19890171989-08-15015 August 1989 Insp Repts 50-387/89-17 & 50-388/89-15 on 890619-23 & 0718 & 19.No Noncompliance Noted.Major Areas Inspected:Mgt Support, Security Program Plans & Audits,Protected & Vital Area Physical Barriers,Emergency Power Supply & Testing ML20247K6691989-05-19019 May 1989 Partially Withheld Notice of Violation Resulting from Investigation to Determine Whether Willful Matl False Statement Was Made in Physical Security Plan (Ref 10CFR2.790(a)) ML20148A5861988-03-14014 March 1988 Notice of Violation from Insp on 880104-0213.Violation Noted:On 880112,areas W/Dose Rates of Up to 400 M/H,Which Constitute High Radiation Areas Not Posted as Required IR 05000387/19880021988-02-19019 February 1988 Insp Repts 50-387/88-02 & 50-388/88-02 on 880104-07.No Violations Noted.Major Areas Inspected:Security Organization & Program Audit,Lighting,Assessment Aids,Access Control, Alarm Stations & Followup to Unresolved Items PNO-I-87-119, on 871223,reactor Scrammed Due to Leak from Intermediate Waterbox Manway C.Caused by Failure of Manway Gasket.Waterbox C Isolated & Spill Terminated.Water in Condenser Bay Area Measured 43 Inches1987-12-24024 December 1987 PNO-I-87-119:on 871223,reactor Scrammed Due to Leak from Intermediate Waterbox Manway C.Caused by Failure of Manway Gasket.Waterbox C Isolated & Spill Terminated.Water in Condenser Bay Area Measured 43 Inches IR 05000387/19870201987-12-0707 December 1987 Insp Repts 50-387/87-20 & 50-388/87-18 on 871027-30.No Violation or Deviation Noted.Major Areas Inspected:Nuclear Matl Control & Accounting,Including Shipping & Receiving, Organization & Operation & Storage & Internal Control IR 05000387/19870151987-11-17017 November 1987 Exam Repts 50-387/87-15OL & 50-388/87-15OL on 870911.Exam Results:One Senior Reactor Operator Candidate Passed Exam. Weaknesses Noted PNO-I-87-079, on 870810,shift Supervisor Relieved of Duties Based on Results of Preliminary Investigation Into Allegation of Being Inattentive During Midnight Shift. Allegations Found Credible.Mgt Meeting W/Nrc Planned1987-08-12012 August 1987 PNO-I-87-079:on 870810,shift Supervisor Relieved of Duties Based on Results of Preliminary Investigation Into Allegation of Being Inattentive During Midnight Shift. Allegations Found Credible.Mgt Meeting W/Nrc Planned ML20214N4621987-05-27027 May 1987 PNS-I-87-008:on 870526,secondary Alarm Station Operator Received Telephone Bomb Threat.Licensee Implemented Search Procedures.Search Completed W/Negative Results.Commonwealth of PA Police Notified IR 05000387/19870051987-05-0707 May 1987 Exam Repts 50-387/87-05OL & 50-388/87-05OL on 870316-19. Exam Results:Three Out of Five Senior Reactor Operators & Two Out of Four Reactor Operators Issued Licenses.Exam & Answer Key Encl PNO-I-87-032, on 870415,Unit 1 Shut Down After Licensee Unable to Successfully Perform Local Leak Rate Test on Three Containment Isolation Valves in Drywell Purge Exhaust Line. on 870416,Unit 2 Tripped Due to MSIV Closure1987-04-16016 April 1987 PNO-I-87-032:on 870415,Unit 1 Shut Down After Licensee Unable to Successfully Perform Local Leak Rate Test on Three Containment Isolation Valves in Drywell Purge Exhaust Line. on 870416,Unit 2 Tripped Due to MSIV Closure IR 05000387/19870071987-03-26026 March 1987 Partially Withheld Physical Security Insp Repts 50-387/87-07 & 50-388/87-07 on 870302-06 (Ref 10CFR73.21 & 2.790).Major Areas Inspected:Programmatic Review of NRC Approved Physical Security & Security Contingency Plans IR 05000387/19870041987-03-10010 March 1987 Insp Repts 50-387/87-04 & 50-388/87-04 on 870209-13.No Violations or Deviations Noted.Major Areas Inspected: Nonlicensed Staff Training IR 05000387/19870021987-03-0505 March 1987 Insp Repts 50-387/87-02 & 50-388/87-02 on 870106-0217.No Violations Noted.Major Areas Inspected:Operations,Licensee Event Followup,Esf Sys Walkdown,Open Item Followup, Surveillance,Maint & Followup of Industry Events IR 05000387/19870031987-03-0404 March 1987 Insp Repts 50-387/87-03 & 50-388/87-03 on 870209-13.No Violations Noted.Major Areas Inspected:Nonradiological Chemistry Program,Including Measurement Control & Analytical Procedures Evaluation IR 05000387/19870011987-02-12012 February 1987 Insp Repts 50-387/87-01 & 50-388/87-01 on 870112-16. No Violations or Deviations Noted.Major Areas Inspected: Environ Monitoring Programs for Operations,Including Mgt Controls for Listed Programs ML20211B1211987-02-0909 February 1987 Notice of Violation from Insp on 861202-870105 IR 05000387/19860271987-02-0909 February 1987 Insp Repts 50-387/86-27 & 50-388/86-30 on 861202-870105. Violation Noted:Inoperability of Station Battery Supplying Common Loads IR 05000387/19860251987-01-30030 January 1987 Insp Repts 50-387/86-25 & 50-388/86-28 on 861117-21. Deficiencies Noted:Failure to Demonstrate Qualification of Valcor High Temp Wire,Rockbestos Coaxial Cables & Raychem Cable Splices.Unresolved Items Listed PNO-I-86-097, on 861210,gas Leakage Initially Detected in Inboard MSIVs & Confirmed on 861211 While Testing Inboard MSIV B.Valve Maintained Closed & Unit Shutdown to Repair Gas Sys.Facility to Be Restarted by 8612141986-12-12012 December 1986 PNO-I-86-097:on 861210,gas Leakage Initially Detected in Inboard MSIVs & Confirmed on 861211 While Testing Inboard MSIV B.Valve Maintained Closed & Unit Shutdown to Repair Gas Sys.Facility to Be Restarted by 861214 PNO-I-86-088, on 861022,during Testing of HPCI Sys,Steam Accidentally Released Into RHR Pump Room.Caused by Two Mispositioned Drain Valves in Piping Associated W/Steam Condensing Mode of RHR Sys.State of PA Notified1986-10-23023 October 1986 PNO-I-86-088:on 861022,during Testing of HPCI Sys,Steam Accidentally Released Into RHR Pump Room.Caused by Two Mispositioned Drain Valves in Piping Associated W/Steam Condensing Mode of RHR Sys.State of PA Notified PNO-I-86-087, on 861022,approx 3,000 Gallons of Liquid Radwaste Spilled on Floor of Radwaste Bldg.Caused by Isolation Valve Leak.Spill Cleaned Up.Decontamination of Affected Areas Underway1986-10-22022 October 1986 PNO-I-86-087:on 861022,approx 3,000 Gallons of Liquid Radwaste Spilled on Floor of Radwaste Bldg.Caused by Isolation Valve Leak.Spill Cleaned Up.Decontamination of Affected Areas Underway ML20205H3331986-08-14014 August 1986 Notice of Deviation from Insp on 860512-16.Appraisals of Unresolved & Open Items Also Encl IR 05000387/19860101986-08-13013 August 1986 Emergency Response Appraisal Repts 50-387/86-10 & 50-388/ 86-10 on 860512-16.One Deviation & Three Unresolved Items Noted:Calibr Procedure for Delta Temp Instrumentation Did Not Include Actual Sensor Calibr IR 05000387/19860131986-07-24024 July 1986 Insp Repts 50-387/86-13 & 50-388/86-13 on 860707-11.No Violations Noted.Major Areas Inspected:Qa & QC Program Changes,Qa Audit Program,Receipt,Storage & Handling Program for Equipment & Matl & Procurement Control Program PNO-I-86-052, on 860717,reactor Scrammed Due to Unidentified Coolant Leakage.Licensee Entered Drywell on 860718 & Identified LPCI Testable Check Valve as Source of Leakage. Repairs to Valve Scheduled for Completion on 8607201986-07-18018 July 1986 PNO-I-86-052:on 860717,reactor Scrammed Due to Unidentified Coolant Leakage.Licensee Entered Drywell on 860718 & Identified LPCI Testable Check Valve as Source of Leakage. Repairs to Valve Scheduled for Completion on 860720 PNO-I-86-039, on 860521,emergency Svc Water Pump C Motor Ran W/O Indication of Flow.Caused by Separation of Suction Bell & Severance of Shaft Near Impeller,Discovered on 860523. Pump Temporarily Repaired.Parts on Order1986-05-27027 May 1986 PNO-I-86-039:on 860521,emergency Svc Water Pump C Motor Ran W/O Indication of Flow.Caused by Separation of Suction Bell & Severance of Shaft Near Impeller,Discovered on 860523. Pump Temporarily Repaired.Parts on Order IR 05000388/19860071986-05-21021 May 1986 Insp Rept 50-388/86-07 on 860407-09.No Violations Noted. Major Areas Inspected:Emergency Preparedness Insp & Observation of partial-scale Annual Emergency Exercise Conducted on 860408 ML20202F3161986-04-0404 April 1986 Notice of Violation from Insp on 860203-0314 IR 05000387/19860011986-04-0101 April 1986 Exam Repts 50-387/86-01 & 50-388/86-01 on 860114-16. Exam Results:All Six Candidates Passed IR 05000387/19860021986-03-27027 March 1986 Insp Repts 50-387/86-02 & 50-388/86-01 on 860203-0314. Violation Noted:Rhr Pump Operated W/O Cooling Water Due to Valve Misalignment & Installation of Expired Squib Valve in Standby Liquid Control Sys PNO-I-86-022, on 860321,util Workman Fell 10 Ft to Subpile Floor Injuring Right Knee While Replacing Control Rod Housing Support.Caused When Platform Grating Gave Way. Worker Decontaminated & Hospitalized1986-03-24024 March 1986 PNO-I-86-022:on 860321,util Workman Fell 10 Ft to Subpile Floor Injuring Right Knee While Replacing Control Rod Housing Support.Caused When Platform Grating Gave Way. Worker Decontaminated & Hospitalized PNO-I-86-023, on 860321,while Replacing CRD Housing Support Underneath Reactor Vessel,Platform Gave Way Injuring & Contaminating Work Person.Employee Decontaminated Onsite Prior to Transfer to Hosp1986-03-24024 March 1986 PNO-I-86-023:on 860321,while Replacing CRD Housing Support Underneath Reactor Vessel,Platform Gave Way Injuring & Contaminating Work Person.Employee Decontaminated Onsite Prior to Transfer to Hosp PNO-I-86-003, on 860115,reactor Manually Scrammed After Power Reduction to 70%.Caused When Oil Observed Spraying from Main Transformer.Oil Spray Caused by Excessive Heat Buildup.Transformer Will Be Inspected & Repaired1986-01-16016 January 1986 PNO-I-86-003:on 860115,reactor Manually Scrammed After Power Reduction to 70%.Caused When Oil Observed Spraying from Main Transformer.Oil Spray Caused by Excessive Heat Buildup.Transformer Will Be Inspected & Repaired PNO-I-85-090, on 851202,Units I & II Tripped from Full & 80% Power,Respectively.Caused by Deenergization of Engineered Safeguards Svc Transformer III & Momentary Loss of Control to Reactor Feed Pumps.Transformer Being Tested1985-12-0303 December 1985 PNO-I-85-090:on 851202,Units I & II Tripped from Full & 80% Power,Respectively.Caused by Deenergization of Engineered Safeguards Svc Transformer III & Momentary Loss of Control to Reactor Feed Pumps.Transformer Being Tested IR 05000387/19850251985-10-21021 October 1985 Exam Repts 50-387/85-25 & 50-388/85-27 on 850806-07.Exam Results:Seven Reactor Operator Candidates Passed Oral, Simulator & Written Sections of Exams PNO-I-85-078A, on 851011,reactor Coolant Spill from RWCU Sys to 779 Ft Elevation of Reactor Bldg Occurred.Caused by Lifting of 150 Psig Precoat Feed Relief Valve.Spill Cleaned & Access to Area Restored1985-10-11011 October 1985 PNO-I-85-078A:on 851011,reactor Coolant Spill from RWCU Sys to 779 Ft Elevation of Reactor Bldg Occurred.Caused by Lifting of 150 Psig Precoat Feed Relief Valve.Spill Cleaned & Access to Area Restored PNO-I-85-078, on 851011,isolation Valve to Low Pressure Sys Piping Opened & Discharge of Reactor Coolant to Cleanup Demineralizer Precoat Pump Area Occurred.Cause Under Investigation.Cleanup in Progress1985-10-11011 October 1985 PNO-I-85-078:on 851011,isolation Valve to Low Pressure Sys Piping Opened & Discharge of Reactor Coolant to Cleanup Demineralizer Precoat Pump Area Occurred.Cause Under Investigation.Cleanup in Progress IR 05000387/19850291985-09-23023 September 1985 Meeting Repts 50-387/85-29 & 50-388/85-24 on 850828 Re Rescheduling of Senior Reactor Operator Licensing Exam. Region Agreed to Administer One Instructor Certification & One Senior Operator Exam on 851120 & 21,respectively PNO-I-85-046, on 850630,reactor Scrammed from 100% Power Due to Generator Load Reject.Caused by Generator Neutral Phase Overvoltage Condition.Test & Repairs Will Be Completed by 8507071985-07-0303 July 1985 PNO-I-85-046:on 850630,reactor Scrammed from 100% Power Due to Generator Load Reject.Caused by Generator Neutral Phase Overvoltage Condition.Test & Repairs Will Be Completed by 850707 IR 05000387/19850141985-05-24024 May 1985 Insp Repts 50-387/85-14 & 50-388/85-14 on 850430-0503.No Violations Identified.Major Areas Inspected:Emergency Preparedness & full-scale Annual Emergency Exercise on 850501 1999-06-09
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i ENCLOSURE NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF civil PENALTY Pennsylvania Power and Light Company (PP&L) Docket Nos. 50-387, 50 388 Susquehanna Stearn Electric Station (SSES) License Nos. NPF-14, NPF-22 Unit 1 and Unit 2 During an NRCinspection conducted from July 1 to August 16,1997, for which exit meetings were held on August 28,1997, and September 11,1997, a violation of NRC requirements was identified. In accordance with the " General Statement of Policy and Procedures for NRC Enforcement Actions," NUREG 1600, the NRC proposes to impose a civil penalty pursuant to Section 234 of the Atomic Energy Act of 1954, as amended (Act),42 U.S.C. 2282, and 10 CFR 2.205. The particular violation and associated civil penalty are set forth below:
10 CFR Part 50, Appendix B, Criterion 11, " Quality Assurance Program", requires, in part, that activities affecting quality be performed under suitably controlled conditions including special controls needed to attain the required quality.
Contrary to the eboe u of July 11,1997, the licensee f ailed to establish adequate controls for activet;un ch acting the quality of the ernergency diesel generators (EDGs).
Specifically, the Somee failed to establish adequate controls for the positio.iing of the speed anciload com.rols of the EDG Woodward governors allowing the 'A' EDG load limit control to be misaligned sometime between June 16,1997, when the load limit setting wasleft in the required 100% load position, and July 11,1997, when the load limit setting was found at approximately 35%. Due to the misalignment, during an accident, the 'A' EDG would not have started with!n the required time and would not have been able to supply the required load as designed. As a result of the
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misalignment, the 'A' EDG was inoperable for an indeterminate period of time between June 16,1997 and July 11, 1997, while both units were operating, contrary to Technical Specification 3.8.1. (01013)
This is a Severity Level 111 violation (Supplement 1).
Civil Penalty - $55,000.
Pursuant to the prov!sions of 10 CFR 2.201, Pennsylvania Power and Light Company (Licensee)is hereby required to submit a written statsment or explanation to the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, within 30 days of the date of this Notice of Violation and Proposed imposition of Civil Penalty (Notice). This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for each alleged violation: (1) admission or denial of the alle0ed violation, (2) the reasons for the violation if admitted, and if denied, the reasons why, (3) the corrective steps that have been taken and the results achieved, (4) the corrective steps that will be taken to avr'id further violations, and (5) the date when full compliance will be achieved, if an adequate reply is not received within the time specified in this Notice, an Order or a Demand for Information may be issued as why the license should not be modified, suspended, or revoked or why such other action as may
% 01200000 990109 PDR ADOCK 05000387 d PDR ,
Enclosure 2 be proper should not be taken. Consideration may be given to extending the response time for good cause shown. Under the authority of Section 182 of the Act,42 U.S.C. 2232, this response shall be submitted under oath or affirmation.
Within the same time as provided for the response required above under 10 CFR 2.201, the Licensee may pay the civil penalty by letter addressed to the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, with a check, draft, money order, or electronic transfer payable to the Treasurer of the United States in the amount of the civil penalty proposed above, or the cumulative amount of the civil penalties if more than one civil penalty is proposed, or may protest imposition of the civil penalty in whole or in part, by a written answer addressed to the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission. Should the Licensee f ail to answer within the time specified, an order imposing the civil penalty willbe issued. Should the Licensee elect to file en answer in accordance with 10 CFR 2.205 protesting the civil penalty, in whole or in part, such answer should be clearly marked as an " Answer to a Notice of Violation" and may: (1) deny the violation listed in this Notice, in whole or in part, (2) demonstrate extenuating circumstances, (3) show error in this Notice, or (4) show other reasons why the penalty should not be imposed, in addition to protesting the civil p3nalty in whole or in part, such answer may request remission or mitigation of the penalty.
In requesting mitigation of the proposed penalty, the factors addressed in Section VI.B.2 of the Enforcement Policy should be addressed. Any written answerin accordance with 10 CFR 2.205 should be set forth separately from the statement or explanation in reply pursuant to 10 CFR 2.201, but may !necaporate parts of the 10 CFR 2.201 reply by specific reference (e.g., citing page end parsgraph numbers) to avoid repetition. The attention of the Licensee is directed to the other provisions of 10 CFR 2.205, regarding the procedure for imposing a civil penalty.
Upon failure to pay any civil penalty due which subsequently has been determined in accordance with the applicable provisions of 10 CFR 2.205, this matter may be referred to the Attorney General, and the penalty, unless compromised, remitted, or mitigated, may be collected by civil action pursuant to Section 234c of the Act,42 U.S.C. 2282c.
The response noted above (Reply to Notice of Violation, letter with payment of civil penalty, and Answer to a Notice of Violation) should be addressed to: Mr. James Lieberman, Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Ono Whita Flint North,11555 Rockville Pike, Rockville, MD 20852-2738, with a copy to the Regional Administrator, U.S.
Nuclear Regulatory Commission, Region I, and a copy to the NRC Resident inspector at the facility that is the subject of this Notice.
Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be prote:ted and a redacted copy of your response that deletes such information. If you request withholding of such material, you must spectiically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the 4
Enclosore 3 disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an a:ceptable response, please provide the level of protection described in 10 CFR 73.21.
Dated at King of Pru;sla, Pennsylvania this 9th day of January,1998 m
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